Event Notification Report for September 29, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/28/1999 - 09/29/1999
** EVENT NUMBERS **
36171 36233 36234 36235 36236 36237
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36171 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/16/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 04:30[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/16/1999|
+------------------------------------------------+EVENT TIME: 01:15[EDT]|
| NRC NOTIFIED BY: DOUG AMTSFIELD |LAST UPDATE DATE: 09/28/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| - Secondary containment integrity lost due to a hatch cover being removed |
| during maintenance activities - |
| |
| At 0115 on 09/16/99, Limerick Generating Station Unit 2 experienced a loss |
| of secondary containment integrity. At the time of the event, the Standby |
| Gas Treatment (SBGT) System was in service. The Reactor Enclosure HVAC |
| System was not in service due to maintenance activities. The SBGT System was |
| unable to maintain reactor enclosure pressure greater than 0.25 inches of |
| vacuum water gauge per technical specifications due to a hatch cover being |
| removed for maintenance inspection activities. This event could have |
| prevented the fulfillment of the safety function of structures or systems |
| that are needed to control the release of radioactive materials or mitigate |
| the consequences of an accident. The hatch cover was reinstalled properly |
| by 0126, and the SBGT System was able to draw a vacuum on the reactor |
| enclosure area greater than 0.25 inches of vacuum water gauge. |
| |
| The licensee informed the NRC resident inspector. |
| |
| * * * RETRACTION AT 0828 ON 09/28/1999 FROM GAMBLE TAKEN BY STRANSKY * * * |
| |
| "This is a retraction of a notification made on 09/16/99 at 0434 hours, |
| (event #36171). This event was reported as a loss of safety function under |
| requirement 10CFR50.72(b)(2)(iii)(D). |
| |
| "Unit 2 Reactor Enclosure HVAC was secured to perform an internal ductwork |
| inspection. SGTS was in service maintaining negative pressure in the Reactor |
| Enclosure. An inspection hatch located outside of secondary containment was |
| removed to perform the internal inspection. This created an unplanned breach |
| of secondary containment. Unit 2 Reactor Enclosure pressure increased but |
| remained negative. The hatch was replaced, and integrity was restored within |
| 11 minutes. |
| |
| "The basis for this retraction is that the safety analysis assumes drawdown |
| of the Reactor Enclosure will take 930 seconds post accident. T.S. |
| 4.6.5.1.1.c.1 surveillance drawdown of the Reactor Enclosure must be |
| completed within 916 seconds (15.26 minutes). Test results indicate drawdown |
| is complete within 2.5 minutes. The sum of the hatch removal time (11 |
| minutes) plus drawdown time (2.5 minutes) totals 13.5 minutes. This is less |
| than the 15.26 minute requirement for establishing rated negative pressure |
| in the Reactor Enclosure. The safety function of mitigating the consequences |
| of an accident was maintained. Therefore, this event is not reportable per |
| the guidance of NUREG-1022, Rev 1." |
| |
| The NRC resident inspector has been informed of this retraction by the |
| licensee. The NRC operations officer notified the R1DO (Silk). |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36233 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 09/28/1999|
| UNIT: [2] [] [] STATE: SC |NOTIFICATION TIME: 00:47[EDT]|
| RXTYPE: [2] W-3-LP |EVENT DATE: 09/27/1999|
+------------------------------------------------+EVENT TIME: 22:33[EDT]|
| NRC NOTIFIED BY: DON KNIGHT |LAST UPDATE DATE: 09/28/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NORMAL POWER SUPPLY TO EMERGENCY ELECTRICAL BUS LOST DUE TO PERSONNEL |
| ERROR |
| |
| Emergency bus E2 was temporarily deenergized after a plant worker bumped 4kV |
| breaker 5215, the normal supply breaker to the bus, causing it to trip. The |
| B emergency diesel generator (EDG) automatically started due to an |
| undervoltage condition on bus E2 and loaded to the bus, restoring power. The |
| licensee reported that the operating residual heat removal (RHR) pump |
| stopped running due to the loss of power to bus E2, but operators manually |
| started the standby pump and restored shutdown cooling within 2 minutes. |
| Reactor coolant system temperature did not increase appreciably during the |
| alignment of the standby RHR pump. |
| |
| The EDG continues to supply power to bus E2 while the licensee makes |
| preparations to transfer back to the normal power supply. The NRC resident |
| inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36234 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/28/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 08:34[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/28/1999|
+------------------------------------------------+EVENT TIME: 07:30[EST]|
| NRC NOTIFIED BY: BRIAN ROKES |LAST UPDATE DATE: 09/28/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO RAW SEWAGE RELEASE TO HUDSON RIVER |
| |
| The licensee notified the New York Department of Environmental Conservation |
| (spill report 9907789) regarding the release of less than ten gallons of |
| sewage to the Hudson River. At approximately 2043 on 9/27/1999, sewage was |
| spilled from the warehouse sewage holding pit to a storm drain, which |
| discharges to the Hudson River. Plant personnel secured the spill source, |
| diked the drain, and cleaned up the residue. The NRC resident inspector has |
| been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36235 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/28/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 12:09[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/28/1999|
+------------------------------------------------+EVENT TIME: 09:09[CST]|
| NRC NOTIFIED BY: RODNEY WHITLEY |LAST UPDATE DATE: 09/28/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SUPPRESSION POOL CLEANUP ISOLATED DURING LEVEL INSTRUMENTATION CALIBRATION. |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "While performing a scheduled calibration of Containment Spent Fuel Pool |
| Level Transmitter, SFC-LT11B, a low level isolation signal was actuated, |
| which resulted in the [Division] II Suppression Pool Cleanup (SPC) isolation |
| valve, RHS-AOV62, isolating. The SPC system responded as designed. |
| Abnormal Operating Procedure, AOP-0003, Automatic Isolations, was entered, |
| and the SPC system was secured per the System Operating Procedure (SOP). |
| Calibration on the level transmitter was secured. The work instructions and |
| referenced calibration data did not include any note or potential isolation |
| of the SPC system. As written, the work instructions only referenced input |
| to a computer point, an alarm, and a control room indication. At the time |
| of this event, the SPC system was not aligned to the dryer pool, and thus |
| was not causing any changes in the bulk water volume of the pool. Operation |
| of the SPC system did not contribute to this event. Also, the SPC system |
| performs a non-safety function. Thus, its isolation did not impact safe |
| plant operation." |
| |
| The licensee notified the NRC resident inspector. |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36236 |
+------------------------------------------------------------------------------+
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/28/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:24[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/27/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:09[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/28/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |TONY VEGEL R3 |
| DOCKET: 0707002 |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOE HALCOMB | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALID ACTUATION OF A 'Q' SAFETY SYSTEM (24-hour report) |
| |
| The following text is a portion of a facsimile received from Portsmouth: |
| |
| "On 09/27/99 at 1609 hours, the X-333 Cascade Building operation personnel |
| received three cascade automatic data processing (CADP) smoke head alarm |
| actuations. These smoke heads were monitoring operating cell 33-2-4 which |
| was promptly taken off stream and shut down. Emergency response personnel |
| monitored the area, and all air sample results for hydrogen fluoride and UF6 |
| were below detectable levels." |
| |
| "This event is reportable due to the valid actuation of a 'Q' safety |
| system." |
| |
| "This event is reportable to the NRC per Safety Analysis Report (SAR) |
| Section 6.9, Table 6.9-1. This is a 24-hour reportable event." |
| |
| "There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event." |
| |
| Portsmouth personnel notified the NRC resident inspector and plan to notify |
| the Department of Energy site representative. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36237 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/28/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 17:43[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 09/18/1999|
+------------------------------------------------+EVENT TIME: 08:48[EST]|
| NRC NOTIFIED BY: GORDON FIEDLER |LAST UPDATE DATE: 09/28/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 0 Startup |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE TO PERFORM RCIC AND HPCI RESET PRIOR TO EXCEEDING 150 PSI DURING |
| UNIT STARTUP |
| |
| On 09/18/99 while the unit was in startup, reactor core isolation cooling |
| (RCIC) and high pressure coolant injection (HPCI) reset was not performed |
| prior to exceeding 150 psi. The reset was performed at 167 psi at 0848, and |
| 150 psi was exceeded at 0830. Therefore, both RCIC and HPCI were inoperable |
| for 18 minutes. |
| |
| The licensee stated that this issue was determined to be reportable at about |
| 1730 on 09/28/99 during performance of a reportability evaluation in |
| accordance with 10 CFR 50.73. The unit is currently operating at 100% power |
| (steady state). |
| |
| The licensee plans to notify the NRC resident inspector and the state |
| (Massachusetts Civil Defense). |
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Page Last Reviewed/Updated Thursday, March 25, 2021